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TM_C_1682_
_17
Designation:C168217Standard Guide forCharacterization of Spent Nuclear Fuel in Support of InterimStorage,Transportation and Geologic Repository Disposal1This standard is issued under the fixed designation C1682;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon()indicates an editorial change since the last revision or reapproval.1.Scope1.1 This guide provides guidance for the types and extent oftesting that would be involved in characterizing the physicaland chemical nature of spent nuclear fuel(SNF)in support ofits interim storage,transport,and disposal in a geologicrepository.This guide applies primarily to commercial lightwater reactor(LWR)spent fuel and spent fuel from weaponsproduction,although the individual tests/analyses may be usedas applicable to other spent fuels such as those from researchand test reactors and mixed oxide(MOX)spent fuel.Thetesting is designed to provide information that supports thedesign,safety analysis,and performance assessment of ageologic repository for the ultimate disposal of the SNF.1.2 The testing described includes characterization of suchphysical attributes as physical appearance,weight,density,shape/geometry,degree,and type of SNF cladding damage.The testing described also includes the measurement/examination of such chemical attributes as radionuclidecontent,microstructure,and corrosion product content,andsuch environmental response characteristics as drying rates,oxidation rates(in dry air,water vapor,and liquid water),ignition temperature,and dissolution/degradation rates.Not allof the characterization tests described herein must necessarilybe performed for any given analysis of SNF performance forinterim storage,transportation,or geological repositorydisposal,particularly in areas where an extensive body ofliterature already exists for the parameter of interest in thespecific service condition.1.3 It is assumed in formulating the SNF characterizationactivities in this guide that the SNF has been stored in aninterim storage facility at some time between reactor dischargeand dry transport to a repository.The SNF may have beenstored either wet(for example,a spent fuel pool),or dry(forexample,an independent spent fuel storage installation(ISFSI),or both,and that the manner of interim storage mayaffect the SNF characteristics.1.4 The values stated in SI units are to be regarded asstandard.No other units of measurement are included in thisstandard.1.5 This standard does not purport to address all of thesafety concerns,if any,associated with its use.It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.1.6 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards,Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade(TBT)Committee.2.Referenced Documents2.1 ASTM Standards:2C170/C170M Test Method for Compressive Strength ofDimension StoneC696 Test Methods for Chemical,Mass Spectrometric,andSpectrochemical Analysis of Nuclear-Grade Uranium Di-oxide Powders and PelletsC698 Test Methods for Chemical,Mass Spectrometric,andSpectrochemical Analysis of Nuclear-Grade Mixed Ox-ides(U,Pu)O2)C859 Terminology Relating to Nuclear MaterialsC1174 Practice for Prediction of the Long-Term Behavior ofMaterials,Including Waste Forms,Used in EngineeredBarrier Systems(EBS)for Geological Disposal of High-Level Radioactive WasteC1380 Test Method for the Determination of Uranium Con-tent and Isotopic Composition by Isotope Dilution MassSpectrometryC1413 Test Method for Isotopic Analysis of HydrolyzedUranium Hexafluoride and Uranyl Nitrate Solutions byThermal Ionization Mass SpectrometryC1454 Guide for Pyrophoricity/Combustibility Testing in1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel andHigh Level Waste.Current edition approved July 1,2017.Published August 2017.Originallyapproved in 2009.Last previous edition approved in 2009 as C1682 09.DOI:10.1520/C1682-17.2For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United StatesThis international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for theDevelopment of International Standards,Guides and Recomme